10 C.F.R. Subpart K—General License for Storage of Spent Fuel at Power Reactor Sites
Title 10 - Energy
Source: 55 FR 29191, July 18, 1990, unless otherwise noted.
A general license is hereby issued for the storage of spent fuel in an independent spent fuel storage installation at power reactor sites to persons authorized to possess or operate nuclear power reactors under part 50 of this chapter. (a)(1) The general license is limited to that spent fuel which the general licensee is authorized to possess at the site under the specific license for the site. (2) This general license is limited to storage of spent fuel in casks approved under the provisions of this part. (3) The general license for the storage of spent fuel in each cask fabricated under a Certificate of Compliance terminates 20 years after the date that the particular cask is first used by the general licensee to store spent fuel, unless the cask's Certificate of Compliance is renewed, in which case the general license terminates 20 years after the cask's Certificate of Compliance renewal date. In the event that a cask vendor does not apply for a cask model reapproval under §72.240, any cask user or user's representative may apply for a cask design reapproval. If a Certificate of Compliance expires, casks of that design must be removed from service after a storage period not to exceed 20 years. (b) The general licensee shall: (1)(i) Notify the Nuclear Regulatory Commission using instructions in §72.4 at least 90 days prior to first storage of spent fuel under this general license. The notice may be in the form of a letter, but must contain the licensee's name, address, reactor license and docket numbers, and the name and means of contacting a person responsible for providing additional information concerning spent fuel under this general license. A copy of the submittal must be sent to the administrator of the appropriate Nuclear Regulatory Commission regional office listed in appendix D to part 20 of this chapter. (ii) Register use of each cask with the Nuclear Regulatory Commission no later than 30 days after using that cask to store spent fuel. This registration may be accomplished by submitting a letter using instructions in §72.4 containing the following information: the licensee's name and address, the licensee's reactor license and docket numbers, the name and title of a person responsible for providing additional information concerning spent fuel storage under this general license, the cask certificate and model numbers, and the cask identification number. A copy of each submittal must be sent to the administrator of the appropriate Nuclear Regulatory Commission regional office listed in appendix D to part 20 of this chapter. (iii) Fee. Fees for inspections related to spent fuel storage under this general license are those shown in §170.31 of this chapter. (2)(i) Perform written evaluations, prior to use, that establish that: (A) conditions set forth in the Certificate of Compliance have been met; (B) Cask storage pads and areas have been designed to adequately support the static and dynamic loads of the stored casks, considering potential amplification of earthquakes through soil-structure interaction, and soil liquefaction potential or other soil instability due to vibratory ground motion; and (C) the requirements of §72.104 have been met. A copy of this record shall be retained until spent fuel is no longer stored under the general license issued under §72.210. (ii) The licensee shall evaluate any changes to the written evaluations required by this paragraph using the requirements of §72.48(c). A copy of this record shall be retained until spent fuel is no longer stored under the general license issued under §72.210. (3) Review the Safety Analysis Report (SAR) referenced in the Certificate of Compliance and the related NRC Safety Evaluation Report, prior to use of the general license, to determine whether or not the reactor site parameters, including analyses of earthquake intensity and tornado missiles, are enveloped by the cask design bases considered in these reports. The results of this review must be documented in the evaluation made in paragraph (b)(2) of this section. (4) Prior to use of this general license, determine whether activities related to storage of spent fuel under this general license involve a change in the facility Technical Specifications or require a license amendment for the facility pursuant to §50.59(c)(2) of this chapter. Results of this determination must be documented in the evaluation made in paragraph (b)(2) of this section. (5) Protect the spent fuel against the design basis threat of radiological sabotage in accordance with the same provisions and requirements as are set forth in the licensee's physical security plan pursuant to §73.55 of this chapter with the following additional conditions and exceptions. (i) The physical security organization and program for the facility must be modified as necessary to assure that activities conducted under this general license do not decrease the effectiveness of the protection of vital equipment in accordance with §73.55 of this chapter. (ii) Storage of spent fuel must be within a protected area, in accordance with §73.55(c) of this chapter, but need not be within a separate vital area. Existing protected areas may be expanded or new protected areas added for the purpose of storage of spent fuel in accordance with this general license. (iii) For purposes of this general license, searches required by §73.55(d)(1) of this chapter before admission to a new protected area may be performed by physical pat-down searches of persons in lieu of firearms and explosives detection equipment. (iv) The observational capability required by §73.55(h)(6) of this chapter as applied to a new protected area may be provided by a guard or watchman on patrol in lieu of closed circuit television. (v) For the purpose of this general license, the licensee is exempt from §§73.55(h)(4)(iii)(A) and 73.55(h)(5) of this chapter. (6) Review the reactor emergency plan, quality assurance program, training program, and radiation protection program to determine if their effectiveness is decreased and, if so, prepare the necessary changes and seek and obtain the necessary approvals. (7) Maintain a copy of the Certificate of Compliance and documents referenced in the certificate for each cask model used for storage of spent fuel, until use of the cask model is discontinued. The licensee shall comply with the terms and conditions of the certificate. (8)(i) Accurately maintain the record provided by the cask supplier for each cask that shows, in addition to the information provided by the cask vendor, the following: (A) The name and address of the cask vendor or lessor; (B) The listing of spent fuel stored in the cask; and (C) Any maintenance performed on the cask. (ii) This record must include sufficient information to furnish documentary evidence that any testing and maintenance of the cask has been conducted under an NRC-approved quality assurance program. (iii) In the event that a cask is sold, leased, loaned, or otherwise transferred to another registered user, this record must also be transferred to and must be accurately maintained by the new registered user. This record must be maintained by the current cask user during the period that the cask is used for storage of spent fuel and retained by the last user until decommissioning of the cask is complete. (9) Conduct activities related to storage of spent fuel under this general license only in accordance with written procedures. (10) Make records and casks available to the Commission for inspection. [55 FR 29191, July 18, 1990, as amended at 64 FR 53616, Oct. 4, 1999; 68 FR 54160, Sept. 16, 2003] The following casks are approved for storage of spent fuel under the conditions specified in their Certificates of Compliance.
Certificate Number: 1000 SAR Submitted by: General Nuclear Systems, Inc. SAR Title: Topical Safety Analysis Report for the Castor V/21 Cask Independent Spent Fuel Storage Installation (Dry Storage) Docket Number: 72–1000 Certification Expiration Date: August 17, 2010 Model Number: CASTOR V/21 Certificate Number: 1002 SAR Submitted by: Nuclear Assurance Corporation SAR Title: Topical Safety Analysis Report for the NAC Storage/Transport Cask for Use at an Independent Spent Fuel Storage Installation Docket Number: 72–1002 Certification Expiration Date: August 17, 2010 Model Number: NAC S/T Certificate Number: 1003 SAR Submitted by: Nuclear Assurance Corporation SAR Title: Topical Safety Analysis Report for the NAC Storage/Transport Cask Containing Consolidated Fuel for Use at an Independent Spent Fuel Storage Installation Docket Number: 72–1003 Certification Expiration Date: August 17, 2010 Model Number: NAC-C28 S/T Certificate Number: 1004. Initial Certificate Effective Date: January 23, 1995. Amendment Number 1 Effective Date: April 27, 2000. Amendment Number 2 Effective Date: September 5, 2000. Amendment Number 3 Effective Date: September 12, 2001. Amendment Number 4 Effective Date: February 12, 2002. Amendment Number 5 Effective Date: January 7, 2004. Amendment Number 6 Effective Date: December 22, 2003. Amendment Number 7 Effective Date: March 2, 2004. Amendment Number 8 Effective Date: December 5, 2005. SAR Title: Final Safety Analysis Report for the Standardized NUHOMS® Horizontal Modular Storage System for Irradiated Nuclear Fuel. Docket Number: 72–1004. Certificate Expiration Date: January 23, 2015. Model Number: NUHOMS®–24P, –52B, –61BT, –32PT, –24PHB, and –24PTH. Certificate Number: 1007. Initial Certificate Effective Date: May 7, 1993. Amendment Number 1 Effective Date: May 30, 2000. Amendment Number 2 Effective Date: September 5, 2000. Amendment Number 3 Effective Date: May 21, 2001. Amendment Number 4 Effective Date: February 3, 2003. Amendment Number 5 Effective Date: September 13, 2005. Amendment Number 6 Effective Date: June 5, 2006. SAR Submitted by: BNG Fuel Solutions Corporation. SAR Title: Final Safety Analysis Report for the Ventilated Storage Cask System. Docket Number: 72–1007. Certificate Expiration Date: May 7, 2013. Model Number: VSC–24. Certificate Number: 1008. Initial Certificate Effective Date: October 4, 1999. Amendment Number 1 Effective Date: December 26, 2000. Amendment Number 2 Effective Date: May 29, 2001. SAR Submitted by: Holtec International. SAR Title: Final Safety Analysis Report for the HI-STAR 100 Cask System. Docket Number: 72–1008. Certificate Expiration Date: October 4, 2019. Model Number: HI-STAR 100. Certificate Number: 1014. Initial Certificate Effective Date: June 1, 2000. Amendment Number 1 Effective Date: July 15, 2002. Amendment Number 2 Effective Date: June 7, 2005. SAR Submitted by: Holtec International. SAR Title: Final Safety Analysis Report for the HI–STORM 100 Cask System. Docket Number: 72–1014. Certificate Expiration Date: June 1, 2020. Model Number: HI–STORM 100. Certificate Number: 1015. Initial Certificate Effective Date: November 20, 2000. Amendment Number 1 Effective Date: February 20, 2001. Amendment Number 2 Effective Date: December 31, 2001. Amendment Number 3 Effective Date: March 31, 2004. Amendment Number 4 Effective Date: October 11, 2005. SAR Submitted by: NAC International, Inc. SAR Title: Final Safety Analysis Report for the NAC–UMS Universal Storage System. Docket Number: 72–1015. Certificate Expiration Date: November 20, 2020. Model Number: NAC–UMS. Certificate Number: 1021. Initial Certificate Effective Date: April 19, 2000. Amendment Number 1 Effective Date: February 20, 2001. SAR Submitted by: Transnuclear, Inc. SAR Title: Final Safety Analysis Report for the TN–32 Dry Storage Cask. Docket Number: 72–1021. Certificate Expiration Date: April 19, 2020. Model Number: TN–32, TN–32A, TN–32B. Certificate Number: 1025. Initial Certificate Effective Date: April 10, 2000. Amendment Number 1 Effective Date: November 13, 2001. Amendment Number 2 Effective Date: May 29, 2002. Amendment Number 3 Effective Date: October 1, 2003. Amendment Number 4 Effective Date: October 27, 2004. SAR Submitted by: NAC International, Inc. SAR Title: Final Safety Analysis Report for the NAC-Multipurpose Canister System (NAC-MPC System). Docket Number: 72–1025. Certificate Expiration Date: April 10, 2020. Model Number: NAC-MPC. Certificate Number: 1026. Initial Certificate Effective Date: February 15, 2001. Amendment Number 1 Effective Date: May 14, 2001. Amendment Number 2 Effective Date: January 28, 2002. Amendment Number 3 Effective Date: May 7, 2003. Amendment Number 4 Effective Date: July 3, 2006. SAR Submitted by: BNG Fuel Solutions Corporation. SAR Title: Final Safety Analysis Report for the FuelSolutionsTM Spent Fuel Management System. Docket Number: 72–1026. Certificate Expiration Date: February 15, 2021. Model Number: WSNF–220, WSNF–221, and WSNF–223 systems; W–150 storage cask; W–100 transfer cask; and the W–21 and W–74 canisters. Certificate Number: 1027. SAR Submitted by: Transnuclear, Inc. SAR Title: Final Safety Analysis Report for the TN–68 Dry Storage Cask. Docket Number: 72–1027. Certificate Expiration Date: May 28, 2020. Model Number: TN–68. Certificate Number: 1029. Initial Certificate Effective Date: February 5, 2003. Amendment Number 1 Effective Date: May 16, 2005. SAR Submitted by: Transnuclear, Inc. SAR Title: Final Safety Analysis Report for the Standardized Advanced NUHOMS® Horizontal Modular Storage System for Irradiated Nuclear Fuel. Docket Number: 72–1029. Certificate Expiration Date: February 5, 2023. Model Number: Standardized Advanced NUHOMS®–24PT1, NUHOMS®–24PT4. [55 FR 29191, July 18, 1990, as amended at 58 FR 17967, Apr. 7, 1993; 58 FR 51770, Oct. 5, 1993; 59 FR 65920, Dec. 22, 1994; 64 FR 48274, Sept. 3, 1999; 64 FR 50872, Sept. 20, 1999; 65 FR 11459, Mar. 3, 2000; 65 FR 12460, Mar. 9, 2000; 65 FR 14810, Mar. 20, 2000; 65 FR 16302, Mar. 28, 2000; 65 FR 17552, Apr. 3, 2000; 65 FR 24630, Apr. 27, 2000; 65 FR 24870, Apr. 28, 2000; 65 FR 25265, May 1, 2000; 65 FR 38717, 38720, June 22, 2000; 65 FR 62599, Oct. 19, 2000; 65 FR 60342, Oct. 11, 2000; 65 FR 75855, Dec. 5, 2000; 65 FR 76898, Dec. 7, 2000; 66 FR 12437, Feb. 27, 2001; 66 FR 13409, Mar. 6, 2001; 66 FR 14486, Mar. 13, 2001; 66 FR 34525, June 29, 2001; 66 FR 43763, Aug. 21, 2001; 66 FR 45752, Aug. 30, 2001; 66 FR 52489, Oct. 16, 2001; 66 FR 56985, Nov. 14, 2001; 66 FR 59534, Nov. 29, 2001; 67 FR 11569, Mar. 15, 2002; 67 FR 46372, July 15, 2002; 67 FR 69989, Nov. 20, 2002; 68 FR 471, Jan. 6, 2003; 68 FR 8447, Feb. 21, 2003; 68 FR 42573, July 18, 2003; 68 FR 70426, Dec. 18, 2003; 69 FR 2500, Jan. 16, 2004; 69 FR 4219, Jan. 29, 2004; 69 FR 50056, Aug. 13, 2004; 70 FR 9504, Feb. 28, 2005; 70 FR 32982, June 7, 2005; 70 FR 37649, June 30, 2005; 70 FR 42488, July 25, 2005; 70 FR 55026, Sept. 20, 2005; 71 FR 14092, Mar. 21, 2006; 71 FR 19810, Apr. 18, 2006]
Title 10: Energy
PART 72—LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE
Subpart K—General License for Storage of Spent Fuel at Power Reactor Sites
§ 72.210 General license issued.
§ 72.212 Conditions of general license issued under §72.210.
§ 72.214 List of approved spent fuel storage casks.
§ 72.216 [Reserved]
§ 72.218 Termination of licenses.
(a) The notification regarding the program for the management of spent fuel at the reactor required by §50.54(bb) of this chapter must include a plan for removal of the spent fuel stored under this general license from the reactor site. The plan must show how the spent fuel will be managed before starting to decommission systems and components needed for moving, unloading, and shipping this spent fuel.
(b) An application for termination of the reactor operating license submitted under §50.82 of this chapter must contain a description of how the spent fuel stored under this general license will be removed from the reactor site.
(c) The reactor licensee shall send a copy of submittals under §72.218(a) and (b) to the administrator of the appropriate Nuclear Regulatory Commission regional office shown in appendix D to part 20 of this chapter.
§ 72.220 Violations.
This general license is subject to the provisions of §72.84 for violation of the regulations under this part.
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